ML070330178

Draft Request for Additional Information

ML070330178
Person / Time
Site:	Salem
Issue date:	02/02/2007
From:	Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2
To:	Chernoff H NRC/NRR/ADRO/DORL/LPLI-2
Ennis R, NRR/DORL, 415-1420
References
TAC MD2786, TAC MD2787
Download: ML070330178 (4)

Text

February 2, 2007 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD2786 AND MD 2787)

The attached draft request for information (RAI) was transmitted on February 2, 2007, to Mr. Jamie Mallon of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Salem Nuclear Generating Station, Unit Nos. 1 and 2, dated August 4, 2006. The proposed amendment would allow the use of blind flanges for containment isolation in the containment purge system supply and exhaust lines, and make corresponding changes to the Technical Specifications (TSs). The amendment would also consolidate the containment isolation requirements by moving the requirements of TS 3/4 6.1.7, Containment Ventilation System, to TS 3/4 6.3.1 (TS 3/4 6.3 for Unit No. 2), Containment Isolation Valves.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.

Docket Nos. 50-272 and 50-311

Attachment:

Draft RAI

MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Senior Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD2786 AND MD 2787)

The attached draft request for information (RAI) was transmitted on February 2, 2007, to Mr. Jamie Mallon of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensees amendment request for Salem Nuclear Generating Station, Unit Nos. 1 and 2, dated August 4, 2006. The proposed amendment would allow the use of blind flanges for containment isolation in the containment purge system supply and exhaust lines, and make corresponding changes to the Technical Specifications (TSs). The amendment would also consolidate the containment isolation requirements by moving the requirements of TS 3/4 6.1.7, Containment Ventilation System, to TS 3/4 6.3.1 (TS 3/4 6.3 for Unit No. 2), Containment Isolation Valves.

This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensee's request.

Docket Nos. 50-272 and 50-311

Attachment:

Draft RAI DISTRIBUTION PUBLIC RidsNrrDorlLpl1-2 RDennig PDI-2 Reading RidsNrrPMREnnis CHarbuck RidsNrrDorlDpr NKaripineni ACCESSION NO.: ML070330178 OFFICE PDI-2/PM NAME REnnis DATE 2/2/07 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT CONTAINMENT PURGE SYSTEM SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated August 4, 2006, PSEG Nuclear LLC (the licensee) submitted an amendment request for Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). The proposed amendment would allow the use of blind flanges for containment isolation in the containment purge system supply and exhaust lines, and make corresponding changes to the Technical Specifications (TSs). The amendment would also consolidate the containment isolation requirements by moving the requirements of TS 3/4 6.1.7, Containment Ventilation System, to TS 3/4 6.3.1 (TS 3/4 6.3 for Unit No. 2), Containment Isolation Valves.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed amendment and would like to discuss the following issues to clarify the submittal.

1) The licensee has stated that the containment purge supply inboard valve and the purge exhaust inboard valve will be replaced by blind flanges. By doing so, the licensee stated that the outboard purge supply and purge exhaust valves will no longer require Appendix J type testing. In the TS changes to Sections 3/4.6.3.1 (applicable to modes 1, 2, 3 and 4), the licensee states that a containment purge valve is not a required containment isolation valve when the flow path is isolated by a blind flange. However, the TS continues to discuss limiting conditions and surveillance requirements applicable to required containment purge isolation valves. Since the valves become required isolation valves only when the blind flanges are removed, and when the blind flanges are removed, what would provide the second isolation for each penetration? Will the inboard isolation valves be reinstalled under this condition? The NRC staff would like to have some more information of the licensee's intent of the required containment purge isolation valve discussions in the TS changes submitted.

2) The licensee has stated that "the outboard supply and exhaust valves will continue to meet the isolation requirements of TS 3.9.4.c, and will isolate on: (1) a Containment Purge and Pressure-Vacuum Relief isolation signal as required by TS SR 4.6.3.1.2.d for Unit 1 and TS 4.6.3.1.2.d for Unit 2, ..." TS 3.9.4.c applies to Refueling Operations and TS SR 4.6.3.1.2.d applies to Modes 1, 2, 3 and 4. The Bases for TS 3/4.9 REFUELING OPERATIONS states that if required, containment purge isolation can be initiated manually from the control room. The new configuration appears to be a relaxation of the TSs since there is only one valve for each penetration available for manual isolation from the control room, where as there were two valves available prior to the intended change (unless it is the intent of the licensee to install the inboard valve during refueling operations). Please address these concerns.

ATTACHMENT

3) The TS changes submitted show that the TS 3/4.6.1.7 requirements will be deleted in their entirety and relocated to TS 3/4.6.3.1. However, Bases 3/4.6.1.7 was kept with changes shown to this section. To avoid any potential confusion, the licensee should delete Bases Section 3/4.6.1.7 and relocate the information to Bases Section 3/4.6.3.